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Category:CORRESPONDENCE-LETTERS
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999 Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span ML20217M5711999-10-20020 October 1999 Forwards Insp Repts 50-445/99-15 & 50-446/99-15 on 990822- 1002.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999 Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred ML20217E7951999-10-12012 October 1999 Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5 ML20212L2891999-10-0101 October 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals. Purpose of GL Was to Obtain Info That Would Enable NRC to Verify That Condition of Licensee SG Internals Comply with Current Licensing Bases TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps ML20212G0721999-09-24024 September 1999 Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site ML20212H0461999-09-24024 September 1999 Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820 ML20212F7481999-09-24024 September 1999 Forwards SER Authorizing Relief from Exam Requirement of 1986 Edition ASME Code,Section XI Pursuant to 10CFR50.55a(a)(3)(ii) for Relief Request A-3 & 10CFR50.55a(g)(6)(i) for Relief Requests B15,16,17 & C-4 ML20212F1041999-09-23023 September 1999 Requests That NRC Be Informed of Any Changes in Scope of Y2K System Deficiencies Listed or Util Projected Completion Schedule for Comanche Peak Steam Electric Station,Units 1 & 2 ML20212E6661999-09-21021 September 1999 Advises That Info Contained in Application & Affidavit, (CAW-99-1342) Re WCAP-15009,Rev 0, Comache Peak Unit 1 Evaluation for Tube Vibration Induced Fatigue, Will Be Withheld from Public Disclosure ML20212D9111999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of CPSES & Did Not Identify Any Areas in Which Performance Warranted Insp Beyond Core Insp Program.Core Insp Plan at Facility Over Next 7 Months.Insp Plan Through March 2000 Encl ML20212A7601999-09-14014 September 1999 Forwards Insp Repts 50-445/99-14 & 50-446/99-14 on 990707-0821.Four Violations Occurred & Being Treated as Ncvs.Conduct of Activities Was Generally Characterized by safety-conscious Operations & Sound Radiological Controls TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999 Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC ML20211P3761999-09-0707 September 1999 Ack Receipt of Ltr Dtd 990615,transmitting Rev 30 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20211L9871999-09-0303 September 1999 Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999 Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl ML20211K2231999-08-31031 August 1999 Forwards Txu Electric Comments of Rvid,Version 2 ML20211J3801999-08-27027 August 1999 Forwards Corrected TS Page 3.8-26 to Amend 66 to Licenses NPF-87 & NPF-89,respectively.Footnote on TS Page 3.8-26 Incorrectly Deleted ML20211G7301999-08-26026 August 1999 Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively ML20211G1081999-08-26026 August 1999 Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure ML20211G3441999-08-25025 August 1999 Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2 ML20211B2861999-08-18018 August 1999 Forwards Insp Repts 50-445/99-13 & 50-446/99-13 on 990720- 23.No Violations Noted.Insp Included Implementation of Licensee Emergency Plan & Procedures During Util Biennial Emergency Preparedness Exercise ML20211C4661999-08-18018 August 1999 Discusses Proprietary Info Re Thermo-Lag.NRC Treated Bisco Test Rept 748-105 as Proprietary & Withheld It from Public Disclosure,Iaw 10CFR2.790 ML20210U3981999-08-17017 August 1999 Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred ML20211C0991999-08-17017 August 1999 Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety ML20211C4571999-08-16016 August 1999 Forwards Omitted Subj Page of Contractor TER TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999 Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802 ML20210R6561999-08-13013 August 1999 Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested ML20210R2221999-08-12012 August 1999 Forwards Insp Repts 50-445/99-10 & 50-446/99-10 on 990510-0628.Violations Noted & Being Treated as Ncvs, Consistent with App C of Enforcement Policy ML20210N1101999-08-0404 August 1999 Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210J2301999-08-0202 August 1999 Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2 ML20210J6071999-08-0202 August 1999 Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2 TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999 Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727 TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999 Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20210K2321999-07-29029 July 1999 Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted ML20210G5861999-07-29029 July 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999 ML20210J0121999-07-27027 July 1999 Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999 Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES ML20210F3121999-07-26026 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, ML20210D8231999-07-23023 July 1999 Forwards Safety Evaluation of Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 ML20210C2931999-07-21021 July 1999 Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20210C3331999-07-16016 July 1999 Forwards Exam Repts 50-445/99-301 & 50-446/99-301 on 990618- 24.Exam Included Evaluation of Six Applicants for Senior Operator Licenses ML20209H2551999-07-16016 July 1999 Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230 1999-09-07
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999 Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999 Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred ML20217E7951999-10-12012 October 1999 Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 ML20212G0721999-09-24024 September 1999 Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site ML20212H0461999-09-24024 September 1999 Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820 TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999 Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC ML20211L9871999-09-0303 September 1999 Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999 Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl ML20211K2231999-08-31031 August 1999 Forwards Txu Electric Comments of Rvid,Version 2 ML20211G1081999-08-26026 August 1999 Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure ML20211G7301999-08-26026 August 1999 Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively ML20211G3441999-08-25025 August 1999 Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2 ML20210U3981999-08-17017 August 1999 Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred ML20211C0991999-08-17017 August 1999 Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999 Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802 ML20210R6561999-08-13013 August 1999 Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested ML20210N1101999-08-0404 August 1999 Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999 Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20210J2301999-08-0202 August 1999 Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2 ML20210J6071999-08-0202 August 1999 Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2 TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999 Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727 ML20210G5861999-07-29029 July 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999 ML20210J0121999-07-27027 July 1999 Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999 Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES ML20210F3121999-07-26026 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, ML20210C2931999-07-21021 July 1999 Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 ML20209H2551999-07-16016 July 1999 Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230 ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20209G0721999-07-13013 July 1999 Forwards Monthly Operating Repts for June 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs of SV Occurred During Reporting Period ML20209F0681999-07-0909 July 1999 Informs That Effective 990514,TU Electric Formally Changed Name to Txu Electric.Change All Refs of TU Electric to Txu Electric on Correspondence Distribution Lists ML20209E0421999-07-0909 July 1999 Forwards Response to NRC Request for Addl Info on LAR 98-010.Attachment 1 Is Affidavit for Info Supporting LAR 98-010 ML20209B6021999-06-30030 June 1999 Submits Second Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Readiness Disclosure for Reporting Status of Facility Y2K Readiness Encl ML20195J6981999-06-15015 June 1999 Provides Addl Info Related to Open Issue,Discussed in 990610 Conference Call with D Jaffe Re ISI Program Relief Request L-1 Submitted by Util on 980220 ML20196A4921999-06-15015 June 1999 Forwards Rev 30 to Physical Security Plan.Rev Withheld,Per 10CFR73.21 ML20195J0491999-06-14014 June 1999 Submits Response to RAI Re Implementation of 1.0 Volt Repair Criteria ML20195J0651999-06-14014 June 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves 05000445/LER-1999-001, Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 11999-06-0808 June 1999 Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 1 ML20195F0091999-06-0808 June 1999 Forwards Response to RAI Re Units 1 & 2 ISI Program for Relief Requests E-1 & L-1.Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2 ML20207E1921999-05-28028 May 1999 Submits Updated Request for NRC Staff to Review & Approve Certain Changes to CPSES Emergency Plan Submitted in 981015 & s Prior to Changes Being Implemented at CPSES ML20207E1711999-05-28028 May 1999 Supplements 990526 LAR 99-004 as TU Electric Believes Extingency Exists in That Proposed Amend Was Result of NOED Granted to Prevent Shudown of CPSES Unit 1 ML20207D9841999-05-26026 May 1999 Requests That NRC Exercise Enforcement Discretion to Allow Cpses,Unit 1 to Remain in Mode 1,power Operation,Without Having Performed Svc Test,Per SR 4.8.2.1d on Unit 1 Battery BT1ED2 ML20195B6351999-05-25025 May 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves TXX-9912, Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise1999-05-21021 May 1999 Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise ML20206U1981999-05-20020 May 1999 Forwards Form 10K Annual Rept,Per 10CFR50.71(b). Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2 ML20196L1931999-05-20020 May 1999 Forwards MOR for Apr 1999 for Cpses,Units 1 & 2.During Reporting Period There Have Been No Failures or Challenges to Power Operated Relief Valves or Safety Valves TXX-9911, Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld1999-05-14014 May 1999 Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld 1999-09-03
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h, j Log il TXX-93353 r r File # 10010 9U9'5 TUELECTRIC October 28, 1993 WHliam J. Cahill, Jr.
Group %cr President U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 P
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) - UNIT 1 DOCKET NO. 50-445 THERMO-LAG LABORATORY TEST RESULTS AND RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION FOR CPSES UNIT 1 REF: 1. TU Electric letter logged TXX-93254 from William J. Cahill, Jr., to NRC ddted July 13, 1993
- 2. NRC letter dated October 29, 1992, from Suzanne C. Black to William J. Cahill, Jr.
Gentlemen:
TU Electric is providing via Enclosures 1 through 5 copies of the laboratory test reports for the most recent TU Electric fire endurance tests. These test reports are listed in Attachment (1). The testing documented in these reports (for Unit 1) was conducted under the auspices of Omega Point Laboratories at San Antonio, Texas, in a manner similar to the Unit 2 tests.
Also enclosed as Enclosure 6 is an engineering report on cable functionality for 1-1/2 incn and 2 inch non-upgraded conduits using the temperature profiles obtained from the existing CPSES fire test results of non-upgraded conduits.
During a meeting on September 20, 1993, your staff raised some questions regarding the effects of a 90 degree C cnnductor temperature on operability of fire tested cables, arid the effects of elevated temperatures on plant cables with respect to c:able aging. TU Electric's responses are provided in Attcchment 2 for information only.
These items are not mcorporated into the TU Electric thermo-lag barrier documeatation as these issues are not part of the acceptance criteria by the NRC ir, reference 1.
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hlhf 9311040328 931028 % /
PDR ADOCK 05000445 6 40 N. Olive Street LB. 81 Dalin,Texn 75201 F pm y
l TXX-93353 !
.-- Page 2 of 2 i Please contact Obaid Bhatty at (817) 897-5839 should you require additional l information. ,
J Sincerely, j 1
8 .) ,.
- William J. Cahill, Jr. ;
, i L
Ahf cwg 1.
By: Roger D. Walker i Manager of Regu'atory Affairs ,
i OB:tg i Attachments Enclosures !
cc w/o enclosures: ;
Mr. J. L. Milhoan, Region IV l Mr. L. A. Yandell, Region IV Mr. T. A. Bergman, NRR t Mr. S. K. West, NRR Resident inspectors ,
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4 1
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ATTACHMENT 1 TO TXX-93353
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Attachment 1 to TXX-93353 :
Page 1 of 1 LIST OF TEST REPORTS NQ. SCHEME # CONFIGURATION
- 1) 11-5 (3) 24"X4" CABLE TRAYS WITH DIFFERENT JOINT j REINFORCEMENT TECHNIQUES j
- 2) 13-2 12"X4" CABLE TRAY (NON-UPGRADE) 2" DIA. CONDUIT (UPGRADE AT RADIAL BENDS ONLY)
- 3) 11-2 24"X4" CABLE TRAY.WITH 1-1/2" AND 2" DIA. CABLE l AIR DROP BUNDLES !
- 4) 11-4 (2) 24"X4" TRAYS (STACKED) WITH CABLE AIR DROPS !'
THROUGH EMBEDDED SLEEVES COVERED BY A " BOX" CONFIGURATION
- 5) 15-2 36"X4" EXPOSED CABLE TRAY WITH (2) INDIVIDUALLY {
WRAPPED 750 MCM CABLES ;
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ATTACHMENT 2 TO TXX-93353 !
ANSWERS TO NRC QUESTIONS FROM THE MEETING OF SEPTEMBER 20, 1993 RE: EFFECTS OF 90 DEGREE C CONDUCTOR TEMPERATURE AND CABLE AGING r
J
_.. . .- ~. - - .
10/23/93 This evaluation addresses two questions raised by the NRC. The first dealt with the effects of a 90 degree C conductor temperature on operability of fire tested cables, and the second; the effects of '
elevated temperatures on plant cables, with respect to cable aging. Both issues, to one degree or another, were evaluated in light of Comanche Peak Steam Electric Station (CPSES) Qualification documents. All Class-1E cables have been qualified for 40 years with the cable operating at a ;
conductor temperature of 90 degrees C. As an example a Cross-link Polyethylene (XLPE) insulated i
Firewall 111 cable was aged at a temperature of 150 degrees C for a period of 941 hours0.0109 days <br />0.261 hours <br />0.00156 weeks <br />3.580505e-4 months <br /> (this is equivalent to more than 45 years of qualified life). Following the thermal aging the cable was exposed to irradiation and a simulated Loss of Coolant Accident (LOCA).The cables were then subjected to an 80v/ mil voltage withstand test for 5 minutes. This amount of voltage stress is equivalent to 80 percent of the factory testing, which was performed at 100 v/ mil. This level of testing is sufficent to demonstrate that the physical and chemical properties of the cable had not been adversely affected by the thermal aging, irradiation aging, or the simulated LOCA tests. The following calculation is i based on characteristics associated with Firewall !!1 cable. ;
The first question we will address will be the effect that the fire test would have on a cable operating at rated current and voltage (i.e. 90 degree C conductor temperature, based on 50 degree C ambient :
and a 40 degree C conductor temperature rise). We will demonstrate analytically that the leakage ,
currents associated with cables operating at 90 degrees C, prior to a fire, are insignificant. If the I cables had been operating at rated current and voltage during the fire test, the cables could be j assumed to be operating at 40 degrees C above ambient. Since there is no stabilized ambient during a fire test, the most accurate approximation would be the average temperature of the cable jacket.
This is a conservative analysis method because of the u.ermal tag between the outerjacket and the conductor. Copper is also an excellent thermal conductor and will act as a temperature averager and thus prevent localized insulation hot spots. The highest temperatures associated with a thermolag ,
configuration, which will be utilized at CPSES, were seen in scheme 9-3 and were associated with l the 1 1/2 and the 2 inch conduits. Toe maximum average temperature associated with the cable jacket ( which we will utilize as the ambient temperture) was 296 degrees F. To determine the conductor temperature we will add 4G degrees C (104 deg F) to the ambient temperature. This will l give us a maximum conductor and insu,3 tion temperature of 400 degrees F. Utilizing the analysis I method contained in ER-EE-006 (see erciosure 6) we have the following:
For the worst case with the current @ 4ma 5 M c b" F '400 D = .118 d :.058 1. = 20 t -(F - 32) + 273 K = 1.65810 9 , jo 6 0
E3': 40 R in 250 1 j a.004 1 2*l 1 IR"' x IR K log - IR' =
E E 3
R t- -R in E A4 : R t= 9.7510 1R' : lR' 10' EA4 = 39 I 1 R in R in\
- + -- + 1 gRt E~ ,
6 R j = 1.2310 I I 3 = 3 91210' % Error 4ma = 4 00 3 " IR 4 10 3
%Enor 4ma = 0 098 l
l page 1 of 5
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Where:
F = Temperature of insulation in degrees F. l D = Diameter over the insulation in inches.
d = Diameter over the conductor in inches.
L = Length of cable exposed to elevated temperatures. '
t = Temperature of insulation in degrees K. i K = Insulation Resistance constant. i E3 = Loop power supply.
R in = NLP card input resistance. ,
1; = Loop power supply current. >
I2 = Transmitter current. ;
1 3 = Leakage current. [
IR = Insulation resistance in Meg ohms - 1000 ft.
I IR' = Insulation resistance for a cable length,in Meg ohms and ft. l IR" = Insulation resistance for a cable length,in ohms and ft. f f
IR* = Insulation resistance for a ideal cable with zero leakage current.
Rt = Transmitter resistance.
l R; = Cable insulation resistance. ;
EA4 = Voltage actoss transmitter at 4 ma.
Therefore; the leakage currents associated with this temperature would be insignificant for this worst case ambient temperature configuration. !
l The second question raised by the NRC dealt with cable aging; specificly, would the elevated l temperatures associated with the fire tests have any adverse affect on an aged cable. We will !
demonstrate anaalytically that these elevated temperatures from the fire have no adverse effect on cable operation during the fire even if the cable were previously aged. Below is an evaluation, utilizing 4 the Arrhenius method, to determine these affects. Since the affects of thermal aging are additive we will utilize the last 11 minutes when the maximum cable jacket temperatures exceeded 386 degrees F. For each minute the maximum temperatures will be utilized. This is conservative since the maximum temperatures occur in the final seconds of the evaluation period, but for evaluation purposes the maximum temperature is being utilized for the entire time period. The following calculation shows that the cable ages approximately 3 years during this time period. Aging the i cable at 150 degrees C for a period of 941 hours0.0109 days <br />0.261 hours <br />0.00156 weeks <br />3.580505e-4 months <br /> is equivalent to a qualified life of more than 45 years.
l Even based on this worst case there is sufficient margin to ensure cable operablity. This evaluatulon l will also demonstrate that, based on actual cable parameters, the amount of additional aging will not
] adversely affect a cable's performance and is bounded by our LOCA test qualification. The calculation j is as follows:
4 t 2 = 0.0167 Ea .= 1.34 K = 8.61710 T j = 90 4 273 1 i page 2 of 5
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10/23/93 i:
Where:
12 = actual exposure (hours) at T 2
~
T 3 = service temperature (deg K) '
E , = activation energy (eV) .
K = Boltzmann's constant = 8.617E-S f i
t 2 represents the actual exposure time at the elevated temperatures and will be calculated at j eleven different points utilizing a matrix.
T 3 is the service temperature of the insulation and corrosponds to the temperature of the conductor, it has been converted from degrees C to degrees K.
I
.' 393 '
401 409 j
'417 !
425 - -
~
F2 434 T2 4
g(F2 - 32 + 273 442 1 451 l 459 I 469 !
478 !
i VA ere: % i tj = equivalent aging (hours) at T 3 ;
T2 = actual exposure temperature (deg K)
F2 = actual exposure temperature (deg F)
F2 represents the last 11 temperatures of the fire test, and each temperature will be evaluated for a period of one minute.
T2 converts the temperatures contained within the matrix to degrees K.
tj is the equation to determine the equivalent aging associated wrth the elevated temperatures.
This equation has been vectorized in order to accommodate the temperature matrix.
page 3 of 5
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.i The equivalent aging in hours is provided in the following matrir: l i
l
' 1
, 368.28 :
I 499.782 !
674.435 905.156 3
1.208 10 t I 3 1.662 10 !
3
, 2.195 10 .l 3
2.984 10 3
3.9 10 l 3
5.415 10 3
7.234 10 t
in order to provide this information in a more useful format the data will be converted to years. l 0.042 !
t 0.057 l 0.077 i 0.103 f 1; 0.138 t
f t )7, = 0.19
.Q 373 l 0.251 !
t 0.341
(
0.445 i f
0618 i
[0.826 i
The equivalent total aging is the sum of the data contained within the matrix: f i
.042 + .057 + .077 + _103 + .138 + .19 + .2514 .341 + .445 + 618 + 826 = 3.088 I I
I Utilizing the same methodology an analysis was performed which evaluated the entire 60 minute time -!
period. The results demonstrated that the total aging associated with the test would have been 3.2 !
years. This amount of additional aging is insignificant and will not have any impact on the results of I this evaluation. ?
I i
page 4 of 5 ;
10/23/93 ;
The insulation temperature utilized within the Arrhenius equations for the qualification of electrical t power cable assumes an insulation temperature of 90 degrees C.This is an extremely conservative !
methodology, typically cables at CPSES are designed with sufficient ampacity margin to prevent the ;
conductor temperature from exceeding 75 degrees C. Allowing for a conductor / insulation temperature ;
of 75 degrees C yields an expected cable life of 253 years. The calculation for this evaluation is I contained on the following page:
t
] t 2 2220730 Ea .: 1.34 K = 8.617104 -
+ 273 T 3 = 90 273 F2 =167 T2= F2 - 32)
'r.d / i 1' t !
j T2 - 273 = 75 t j rt 2e JI(Fi T 2" )' t t I t g = 40 t3 4rs ' 24 365 g
J !
t 2 Ts = 253.508 '
] 3 1
i Where: ,
1
)
t tj = Equivalent aging (hours) at T j ~
i t 2 = Actuaul exposure (hours) at T, l T j = Service temperature (deg K).
T2 = Actual exposure temperature (deg K).
F2 = Actual exposure temperature (deg F). >
E, = Activation energy.
1 m = riquivalent aging in years. l
< 3.rs= Actual exposure in years.
~
I i
2 Since Arrhenius and aging effects are cumulative it is acceptable to subtract the amount of aging due to exposure to the fire temperature from the expected life. This will yield and expected life wellin excess of the required 40 year operating life of CPSES.
CONCLUSION:
4 The foregoing analysis demostrates that the answer to either question is that the cable would perform ris intended fuction. Neither the effects of operating the cable at rated current and voltage during the fire test nor the effects due to cable aging, would adversely impact the cable performance.
I 1
i 1
page 5 of 5 i
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